ML20199J321
| ML20199J321 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/20/1997 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199J326 | List: |
| References | |
| TAC-M95370, NUDOCS 9711280117 | |
| Download: ML20199J321 (8) | |
Text
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4 UNITED STATES s
NUCLEAR REGULATORY COMMIS810N WASHINGTON, D.C. 3000HSM
\\e...+
ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.136 License No. NPF-38 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated February 6, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; that the activities authorized by There is reasonable assurance (i)ithout endangering the health and C.
this amendment can be conducted w safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
1he issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
971t290117 971120 PDfit ADOCK 05000382 P
'.. 2.
Accordingly, the Itcense is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of facility Operating License No. NPF-38 is hereby amended to read as follows:
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.136, and the Environmental Protection Plan conta'ned in A)pendix D, are hereby incorporated in the license.
The licensee stall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULA10RY COP 911SS10N ch+
n ph Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 20, 1997
I l
ATTACHMENT TO LICENSE AMENDMENT NO.136 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following Jages of the Appendix A Technical Specifications with the attached pages. T1e revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
l REMOVE PACES INSERT PAGES 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-26 3/4 3-26 3/4 10-2 3/4 10-2 3/4-10-4 3/4 10-4
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---.---e wa-w-
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a v -
--a
l TABLE 3.3-4 i
l-DIGINEDtED SAFETY FEATURES ACTUATION SYSTEM INSTRWENTATIM TRIP VALilES l
r ALLOWOLE FUNCTI0llAL INIIT TRIP SETPOINT VALUES 1
1.
SAFETY IIDECTION (SIAS) j a.
Manual (Tris Buttons)-
llot Applicable Not Applicable.
b.
Contaisument Pressure - High
$ 17.1 psia s 17.4 psia
'l c.
Pressurizer Pressure - Low 2 1684 psia"'
1 1649.7 psia"3 l
b
- d.
Automatic Actuation Logic Not Applicable IIet Applicable
?
j 2.
CONTAIIGENT SPRAY (CSAS) a.
Manual (Trip Buttons)
Not Applicable list Applicable 4
i s 17.7 psia s 218.0 psia i
b.
~ Containment Pressure - High-High c.
Automatic Actuation Logic flot Applicable IIst Applicable
[
3.
CONTAIISENT ISutATICII (CIAS)
I a.
Manual CIAS (Trip Buttons) flot Applicable Ilot Applicable
[
i i
b.
Containment Pressure - High s 17.1 psia s 17.4 psia l
[
i l
c.
Pressurizer Pressure - Low 2'1684 psia"3 21649.7 psia"3 l
i-d.
Automatic Actuation Logic Not Applicable Not Applicable i
i 4.
MRIN STEAM LIIIE ISOLATION i
a.
Manual (Trip Buttons) flot Applicable IIst Applicable l
b.
Steam Generator Pressure - Low 2 764 psia
2 749.9 psia
l 4
c.
Containment Pressure - High 5 17.1 psia s 17.4 psia l
j d.
Automatic Actuation Logic Ilot Applicable
. IIst Applicable I
i MRTENFORD - WIIIT 3 3/4 3-19 AWEIENENT 110.136 i
t
TABLE 3.3-4 (Continued)
ENGINEERED SAFETY FEATURES ACTUATION 5Yutm INSTRUNENTATION TRIP VALUES ALLOWABLE FUNCTIONAL UNIT TRIP VALUE VALUES 5.
SAFETY INJECTION SYSTEM SUNP RECIRCULATION (RAS) a.
Manual RAS (Trip Buttons)
Not Applicable Not Applicable b.
Refueling Water Storage Pool - Low 10.0% (57,967 gallons) 9.08% (52,634 gallons) c.
Automatic Actuation logic Not Applicable Not Applicable t
6.
LOSS OF POWER a.
4.16 kV Emergency Bus Undervoltage 1 3245 volts 1 3245 volts (Loss of Voltage) b.
480 V Emergency Bus Undervoltage 1 372 volts 1 354 volts i
c.
4.16 kV Emergency Bus Undervoltage (Degraded Voltage) 1 3875 volts 1 3860 volts 7.
Manual (Trip Buttons)
Not Applicable Not Applicable b.
Steam Generator (l&2) Level - Low 2 27.4%"'
1 26.48%"'
l l
c.
Steam Generator & - High (SG-1 > SG-2) $ 123 psid g 134 psid d.
Steam Generator & - High (SG-2 > SG-1) S 123 psid s 134 psid e.
Steam Generator (l&2) Pressure - Low 1 764 psia'*'
1 749.9 psia (2' l
f.
Automatic Actuation Logic Not Applicable Not Applicable g.
Control Valve Logic (Wide Range SG Level - Low) 1 36.3%"' "'
1 35.3%"' "3 WATERFORD - UNIT 3 3/4 3-20 Amendment No.1",,1 3)36
i i
l 4
i i
TABLE 4.3-2
]
j g
ENGIIEERED 5AFETY FEATURES ACTUATION SYSTEM INSTRSENTAIGIl SWRVEILLAIG RE4WIRBENTS h
.i i
Q CNANNEL NOBES FOR WIOl h
CHRIGIEL CHANNEL FilNCTIONAL SURVEILLANCE H
FINICTIONAL INIIT CHECK CALIBRATION TEST 15 REQUIRED l
E ji 4
1.
SAFETY IIUECTICII (SIAS) d i
a.
Manuel (Trip Buttons)
N.A.
N. A.
R 1, 2, 3, 4 ij
]
b.
Centalsament Pressure - Nigh 5
R S
1, 2, 3 i!
c.
Pressurizer Pressure - Low 5
R Q
1, 2, 3 d.
Automatic Actuation Logic l
l (emcept sedsgroup relays)
N.A.
N.A.
Q(2) 1, 2, 3 Actuation Se6 group Relays N.A.
N. A.
II(3) (5) 1, 2, 3 t
2.
CONTAllSENT SPNRY (CSAS) a.
Manuel (Trip Buttons)
N.A.
N.A.
R 1, 2, 3, 4 g
- b.. Containment Pressure -
4 Nigh - Nigh 5
R Q
1, 2, 3 l
c.
Automatic Actuetten Logic T
(emcept sehgroep relays)
N.A.
N.A.
Q(2) 1, 2, 3 j
U Actuetien Se6groep Nelays N.A.
N.A.
M(1) (3) 1, 2, 3 I
3.
COIITAIISENT ISOLATION (CIAS) l a.
Manuel CIAS (Trip Buttons)
N.A.
N.A.
R 1,2,3,4 I
b.
Containment Pressure - Nigh 5
R Q
1,2,3 l
c.
Pressurizer Pressure - Low 5
R S
1, 2, 3 j
d.
Automatic Actuation Logic (except se6 group relays)
N.A.
N.A.
Q(2) 1, 2, 3 g
Actuetien Se6groep Nelays M.A.
N.A.
M(1) (3) 1, 2, 3 h
4.
DWLIN 5T051 LIIE ISOLATION a.
Mensal (Trip Buttons)
N.A.
N. A.
R 1, 2, 3
, g o
b.
Steam Generator Pressure - Los 5 R
Q 1, 2, 3 3
- 5 c.
Containment Pressure - Nigh 5
R Q
1, 2, 3 i
d.
Automatic Actuation Logic
,j g *M (except subgroep relays)
N.A.
N.A.
Q(2) 1, 2, 3 L
Actuation Se6groep Nelays N.A.
N.A.
M(1) (3) 1, 2, 3 ji l
1 O
TABLE 4.3-2 (Continued)
ENGINEERED SAFETY FEATL9ES ACTUATION SYSTEM INSTRUNENTATION SURVEILLANCE REDUIRDGITS CHAMEL MIDES FOR WICM CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FtWCTIONRL UNIT CHECK CALIBRATION TEST IS REGUIRED 5.
SAFETY INJECTION SYSTEM RECIRCULATION (RAS) a.
Manual RAS (Trip Buttons)
N.A.
N.A.
R I, 2, 3, 4 b.
Refueling Water Storage
. Pool - Low 5
R Q
1, 2, 3, 4 c.
Automatic Actuation Logic (except subgroup relays)
N.A.
M.A.
Q(2) 1, 2, 3, 4 Actuation Subgroup Relays M.A.
N.A.
M(1) (3) 1, 2, 3, 4 6.
LOSS OF POWER (LOV)
[
a.
4.16 kV Emergency Bus i
Undervoltage (Loss of i
Voltage)
N.A.
R D(4) 1, 2, 3 l
b.
480 V Emergency Bus Undervoltage (Loss of Voltage)
N.A.
R P(4) 1, 2, 3 l
c.
4.16 kV Emergency Bus Undervoltage (Degraded Voltage)
N.A.
R' D(4) 1, 2, 3 I
i i
i j
I l
l l
WATERFORD - UNIT 3 3/4 3-26 Amendment No. 69,M,136
.(
l I
3/4.30 SPECIAL TEST EXCEPTIONS
/*3/4.10.1 $HUTDOW MRGIN LIMITING CONDIT]DN FOR OPERATION 3.10.1 The $ NUT 00W MARGIN requirement of Specificatioti 3.1.1.1 or 3.1.1.2 may be suspended for measurement of CEA worth and SHUTDOWN MRGIN provided reactivity equivalent to at least the highest estimated CEA worth is evallable for trip insertion free OPERABLE CEA(s).
APPLICABILITY: MODES 2 AND 3*.
ArTION:
a.
With arty full-length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immedt-ately initiate and continue boration at greater than er equal to 40 gpa of a solution containing greater than or equal to 1720 ppm boron or its equivalent until the SHUTDOW ERGIN required by Specification 3.1.1.1 is restored, b.
With all full-length CEAs fully inserted and the reactor suberities) by less than the above reactivity equivalent immediately initiate and continue boration at greater than or equa,l to 40 gpa of a solution containing greater than or equal to 1720 ppe boron or its equivalent until the SHUTDOW MRGIN required $y Specification 3.1.1.2 is restored.
$URVEILLAUCE REQUIREMENTS 4.10.1.1 The position of each full-length and part-length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripad from at least the 50% withdrawn position within 7 days prior to reducing tw SHUTDOW MRGIN to less than the limits of SpecificMtion 3.1.1.1.
" Operation in MODE 3 shall be limited to 6 consecutt've hours.
WATERFORD - LINIT 3 3/4 10-1 AME gE g h l
SPECIAL TEST EXCEPTIONS 314.1.0. H MODERATOR "EMPERATURE COEFFICIENT GROUP HEIGHT. INSERTION. AND fg [R D STR1RUTION LLMITS LIMITIPG cannITION FOR OPERATION 3.10.2 The moderator temperature coefficient, group height, insertion, and power distribution limits of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.1.3.7. 3.1.2, 3.2.3, 3.2.7, and the Minimum Channels OPERA 8LE requirement of Functional Unit 15 of Table 3.3-1 may be suspended during the perfomance of PHYSICS TESTS provided:
e.
The THERMAL POWER is restricted to the test power plateau which shall not exceed 85% of RATED THERMAL POWER, and b.
The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below.
APPLICABILITY: MODES 1 and 2.
ACIIM:
With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.1.3.7, 3,2 2, 3.2.3, 3.2.7, and the Minimum Channels OPERABLE requirement of Fur.etional Unit 15 of Table 3.3-1 are suspended, either:
a.
Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.
Se in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS ir, which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.1.3.7, 3.2.2, 3.2.3, 3.2.7, or the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended and shall be verified to be within the test power plateau.
4.10.2.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detection Monitoring System pursuant to the requirements of Specifications 4.2.1.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.1.3.7 3.2.2, 3.2.3, 3.2.7, or the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 are suspended.
WATERFORD - UNIT 3 3/4 10-2 Amendment No. 44,136
~s iPECIAL TEST EXCEPTIONS 3/4.10.3 REACTOR COOLANT LOOPS LIMITING COND] TION FOR OPERATION 3.10.3 The noted requirements of Tables 2.2-1 and 3.31 may be suspended during the perfomance of startup and PHYSICS TESTS, provided:
a.
The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and either b.
The reactor trip setpoints of the OPERABLE power level channels are set at less than or equal to 20% of RATED THERMAL POWER, or c.
The core protection calculator operating bypass pemissive setpoints are increased to greater than the logarithmic power-hi trip setpoint specified in Table 2.21 and less than 5% RATED THERMAL POWER.
APPLICABILITY: During startup and PHYSICS TESTS.
ACTION:
With the THERMAL POWER greater than 5% of RATED THERMAL POWER, ismediately trip the reactor.
SURVEILLANCE REQUIREMENTS g
4.10.3.1 The THERMAL POWER shall be detemined to be less than or equal to 5%
of RATED THERMAL POWER at least once per hour during startup and PHYSICS TESTS.
4.10.3.2 Each wide range logarithmic and power hvel neutron flux monitoring channel shall be subjected to a CHANNEL FUNCTIOD.t TEST within U hours prior to initiating startup and PHYSICS TESTS.
k WATERFORD - UNIT 3 3/4 10-3 AMENDMENT NO. 11 M0 I
SPECIAL TEST EXCEPTIONS 3/4.10.4 CENTER CEA MISALIGMENT 4
LIMITING CONDITION FOR OPERATION 3.10.4 The requirements of Specifications 3.1.3.1 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS to determine the isothermal i
temperature coefficient, moderator temperature coefficient, and power coefficient provided:
a.
OnlythecenterCEA(CEA#1)ismisaligned,and b.
The limits of Specification 3.2.1 "e maintained and de+ ermined as specified in Specification 4.19.4.2 below.
APfLICABILITY: MODES I and 2.
ACTION:
With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1..: I and 3.1.3.6 are suspended, either:
a.
Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.
Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.10.4.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the raquirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended and shall be verified to be within the test power plateau.
4.10.4.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detection Monitoring System pursuant to the requirements of Specifications 4.2.1.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended.
WATERFORD - UNIT 3 3/4 10-4 AMENDMENT NO. 136
.